05000278/LER-2005-003, Re Residual Heat Removal System Small Bore Piping Leak Due to Weld Deficiency
| ML053110153 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/28/2005 |
| From: | Grimes J Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 05-003-00 | |
| Download: ML053110153 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2782005003R00 - NRC Website | |
text
ExebIon SM Exelon Nuclear Telephone 717.456.7014 Nuclear Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road Delta, PA 17314-9032 1 OCFR 50.73 October 28, 2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station (PBAPS) Unit 3 Facility Operating License No. DPR-56 NRC Docket No. 50-278
Subject:
Licensee Event Report (LER) 3-05-03 This LER reports a leak in the Reactor Coolant System identified during the 151h Refueling Outage for Unit 3. In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that are planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact us.
Sincerely, Joseph P. Grimes Plant Manager Peach Bottom Atomic Power Station JPG/djf/CR 375299 Attachment cc:
PSE&G, Financial Controls and Co-owner Affairs R. R. Janati, Commonwealth of Pennsylvania INPO Records Center S. Collins, US NRC, Administrator, Region I R. I. McLean, State of Maryland US NRC, Senior Resident Inspector CCN 05-14099 CX-an
NRC FPRM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 62004)Estimated burden per resonse to comply wh this mandaorollection request 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are Incorporated into the licensing process and fed back to Industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear LI C ENS EE EV ENT R EPO RT (LER)
RntegulatoryCommissionWashingtonDC 20555-OOO1i. or biy Intemet e-mail to LICE SEE VENTREPO T (L R)lnfocotlects~nrc.gov. and to the Desk Officer, Office a~
Information and RegulatoryAffairs. NEOB-10202, (3150-0104), Officeof ManagementandBudget, Washington, DC 20503. If a means used to Impose an Information collection (See reverse for required number of does not displaya currentlyvalid OMB control number, the NRC may not conduct or sponsor, and a person Is not required to respond to. the Information digits/characters for each block) collection.
- 3. PAGE Peach Bottom Atomic Power Station, Unit 3 05000 278 OF 5
- 4. TITLE Residual Heat Removal System Small Bore Piping Leak due to Weld Deficiency
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILMES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NSEUENTIAL ORE. MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 09 20 2005 05 03 0
10 28 2005 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)
El 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 3 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4)
D 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) a 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 0 E 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER 03 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or In NRC Formn 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Incdude Area Code)
PBAPS Unit 3, James Mallon, Regulatory Assurance Manager 1717-456-3351CAUSE SYSTEM COM PONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On 9/20/05 at approximately 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, Licensed Operations personnel determined that a small amount of Reactor Coolant System (RCS) pressure boundary leakage existed on Unit 3. This determination was made based on review of a Primary Containment inspection performed subsequent to a Reactor shutdown on 9/19/05 for a Refueling Outage. The RCS pressure boundary leakage was determined to exist on a one-inch equalizing line for the 'A' Residual Heat Removal injection testable check valve located within the normally inaccessible Primary Containment. The leak was at a pipe coupling socket weld. The leak was determined to exist during Unit 3 Cycle 15 operations. The peak Containment unidentified leakage rate totaled approximately I gpm during the operating cycle. The cause of the weld deficiency was due to lack of fusion associated with the weld. The welded joint was replaced and appropriately inspected and tested successfully during the Unit 3 Refueling Outage. An extent of condition evaluation was performed for additional inspections associated with similar welds on Unit 3. Other evaluations will be performed for Unit 2 similar welds. There were no actual safety consequences associated with this event.
NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
Cause of the Event
The RCS leakage was due to a socket weld crack in the one-inch pipe coupling associated with the 'A' RHR loop testable check valve equalizing line. The crack extended approximately 160 degrees around the circumference of the weld. The cause of the weld failure was due to lack of fusion (i.e. a weld flaw) associated with the root weld. The lack of fusion was the crack initiator. The lack of fusion extended approximately 120 degrees around the weld. Laboratory analysis indicated that the crack originated from the weld interior at the weld root. The lack of fusion at the root of this weld reduced the strength of the weld.
This weld was completed as part of a Recirc / RHR pipe replacement project performed on Unit 3 in the 1987-1989 time period.
Further cause analysis of the failed weld is being performed in accordance with the Corrective Action Program.
Corrective Actions
The welded joint was replaced and appropriately inspected and tested successfully during the Unit 3 Refueling Outage. The inspections included Non-Destructive Examinations (NDE).
An extent of condition evaluation was performed for additional inspections associated with similar welds on Unit 3. The evaluation identified other welds most susceptible to the failure identified. This sample size was beyond that which is required by the ASME code, but was considered prudent. Therefore, ultrasonic testing of similar small-bore welds was performed during the Unit 3 Refueling Outage. Additional indications were also identified on similar socket welds on the 'A' and 'B' loops of RHR. Repairs were completed for these indications and inspected / tested successfully during the Unit 3 Refueling Outage.
Further extent of condition reviews (including Unit 2) are being performed in accordance with the Corrective Action Program. This includes the consideration of enhanced programmatic strategies to identify small bore piping degraded welds.
Previous Similar Occurrences There were no previous LERs identified involving RCS leakage involving similar one-inch piping.
A;'Exeloe),nAA Exelon Nuclear Telephone 717.456.7014 NuE eeaIr Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road IO CFR 55.33 Delta. PA 173 14-9032 November 1, 2005 Mr. Samuel J. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region I 475 Allendale Rd.
King of Prussia, PA 19406-1415 Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Request for Approval for Generic Fundamentals Examination (GFE)
Administration The purpose of this letter is to request approval to have the 14 individuals listed on Attachment I take the BWR Generic Fundamentals Examination section of the written operator licensing examination to be administered on 12/7/05. All of the listed individuals on Attachment I are enrolled in the PBAPS operator licensing training program and will have completed the generic fundamentals portion of this program by the examination date.
The following personnel will have access to the examinations before they are administered:
Name Title Peter Gigliotti Operations Training - Exam Proctor Richard Edens Operations Training - Exam Coordinator / Reviewer Bruce Hennigan Operations Training - ILT Principle Instructor Jack Popielarski Operations Training - Manager Please address the examinations to the overnight mail address below:
Bruce Hennigan, Operations Training - ILT Principal Instructor Mail Stop: PBTC Peach Bottom Atomic Power Station 1848 Lay Rd.
Delta, PA 17314 If you have any questions, feel free to contact Mr. Jack Popielarski at 717-456-3822.
Sincerely, Robert C. Braun Site Vice President Peach Bottom Atomic Power Station
cc:
F. L. Bower, Senior Resident Inspector, USNRC, PBAPS R. R. Janati, Commonwealth of Pennsylvania Document Control Desk, USNRC, Washington DC R. J. Conte, USNRC Region I Chief, Operations Branch, DRS CCN: 05-14102 Attachment